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ASME Boiler and Pressure Vessel Code, Sec.XI, Appendix G, Fracture Toughness Criteria for Protection against Failure, American Society of Mechanical Engineers, 2010.
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2 |
10CFR50, Appendix G, Fracture Toughness Requirements, Nuclear Regulatory Commission, 1997.
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IAEA, Status of Small and Medium Sized Reactor Designs, International Atomic Energy Agency, 2012.
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4 |
S.Y. Park, et al., P-T limit curve of reactor pressure vessel with nozzle corner crack, in: 21st International Conference on Structural Mechanics in Reactor Technology (SMiRT), 2011.
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S. Yin, et al., Fracture analysis for reactor pressure vessel nozzle corner crack, in: 22nd International Conference on Structural Mechanics in Reactor Technology (SMiRT), 2013.
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USNRC Regulatory Guide 1.99 Rev.2, Radiation Embrittlement of Reactor Vessel Materials, U.S. Nuclear Regulatory Commission, 1988.
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7 |
S.B. Choi, et al., Evaluation of constraint effect due to crack location and bottom head shape, in: Proceedings of the ASME 2016 Pressure Vessel & Piping Division Conference, 2016.
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8 |
ABAQUS, User's Manual, 2016.
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9 |
ASME Boiler and Pressure Vessel Code, Sec.II Table D, Properties, American Society of Mechanical Engineers, 2007.
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10 |
Korea Electric Power Industry Code, MIZ Appendix G, Fracture Toughness Criteria for Portection against Failure, Korea Electric Association, 2010.
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11 |
S.B. Choi, et al., Parametric study on pressure-temperature limit curve, in: Proceedings of the ASME 2016 Pressure Vessel & Piping Division Conference, 2016.
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